Development of the diagnostic tools for the COMPASS-U tokamak and plans for the first plasma

Weinzettl, V.; Bílková, P.; Ďuran, I.; Hron, M.; Pánek, R.; Markovič, T.; Varavin, M.; Cavalier, J.; Kovařík, K.; Torres, A.; Matveeva, E.; Böhm, P.; Ficker, O.; Horáček, J.; Čeřovský, J.; Zaja̧c, J.; Adámek, Jiřı́; Dimitrova, M.; Imríšek, M.; Šos, M.; Tomesova, Eva; Vondráček, P.; Mikszuta-Michalik, Katarzyna; Svoboda, Jakub; Naydenkova, D.; Bogár, K.; Caloud, J.; Ivanov, Vladislav; Lukes, S.; Podolník, A.; Bogar, O.; Entler, Slavomír; Havránek, A.; Preinhaelter, J.; Jaulmes, F.; Dejarnac, R.; Balner, V.; Veselovsky, V.; Belina, Pavel; Kral, M.; Gerardin, J.; Vlček, Jiřı́; Tadros, M.; Turjanica, Pavel; Kindl, Vladimir; Reboun, Jan; Rowan, W. L.; Houshmandyar, Saeid; Scholz, M.; Bielecki, J.; Makowski, Dariusz; Chernyshova, M.; Cipciar, D.

doi:10.1016/j.fusengdes.2023.113545

Cited by 2 publications

(2 citation statements)

References 53 publications

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“…Finally, the development and operation of tokamak and diagnostics systems [18] capable of withstanding such elevated temperatures represents a vital aspect of preparation for the operation of next-step devices.…”

Section: Hot First Wall Operationmentioning

confidence: 99%

“…For details of the machine design we refer the reader to an engineering overview [17]. Similarly, the progress in diagnostics design has been already reported [18]. The purpose of this work is to present the priority physics topics, which will be investigated at this facility, to describe the main scenarios of the future machine and a brief literature overview of the respective topics.…”

Section: Introductionmentioning

confidence: 96%

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COMPASS Upgrade: a high-field tokamak for ITER- and DEMO-relevant research

Komm,

Jaulmes,

Grover

et al. 2024

Nucl. Fusion

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In order to achieve their goals, future thermonuclear reactors such as ITER and DEMO are expected to operate plasmas with high magnetic field, triangularity and confinement. With the objective to address the corresponding challenges, a concept of the high field (BT ≤ 5 T), high current (IP ≤ 2 MA) COMPASS Upgrade tokamak was established and the device is currently being constructed in Prague, Czech Republic.This contribution provides an overview of the priority physics topics for the future physics programme of COMPASS Upgrade, namely: (i) characterisation of alternative confinement modes, (ii) power exhaust including liquid metals, (iii) operation with hot first wall and (iv) influence of plasma shape on pedestal stability and confinement. The main scenarios are presented, as predicted by METIS and FIESTA codes. Pedestal pressure and density are estimated using EPED, multi-machine semi-empirical scalings and a neutral penetration model. Access to detachment is estimated using a detachment qualifier.

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Section: Hot First Wall Operationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 96%

COMPASS Upgrade: a high-field tokamak for ITER- and DEMO-relevant research

Komm,

Jaulmes,

Grover

et al. 2024

Nucl. Fusion

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Digitizer hardware for magnetic data acquisition on COMPASS-U

Oliveira,

Torres,

Batista

et al. 2023

EPJ Web Conf.

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This paper presents the design and development of a modular digitizer prototype tailored for magnetic sensor data acquisition within the COMPASS-U tokamak facility, an upcoming experiment in Prague that will operate under conditions relevant to future experiments like ITER and DEMO. The magnetic diagnostic data serves a dual role, both for scientific analysis and real-time control. Due to the latter, the data integrity and fidelity is paramount for the plasma performance and overall safety of the fusion experiment. The digitizer prototype showcases a contemporary adaptation of prior board designs deployed in large fusion experiments such as JET and W7X. Leveraging the advanced capabilities of the Xilinx K26 Zynq Ultrascale+ System-on-Module, this digitizer interfaces seamlessly with ADC modules, facilitating real-time data pre-processing. The digitizer sends data to the real-time control system by a high-speed PCI Express interface. A distinctive facet of the design lies in its configurable clock architecture, allowing versatile distribution of clocks and triggers to accommodate diverse experimental scenarios. The inherent modularity and dynamic reprogramming of the hardware mean the system can find applications beyond its intended role. These include data acquisition for other diagnostics or application in different experiments. The modularity and flexibility and scalability of this design position it as invaluable candidate for high-volume data acquisition systems with a high number of isolated channels at a low cost per channel. As the scientific community endeavors towards advancing fusion technologies, the presented modular digitizer design stands poised to make significant contributions in magnetic diagnostics and real-time control applications.

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Development of the diagnostic tools for the COMPASS-U tokamak and plans for the first plasma

Cited by 2 publications

References 53 publications

COMPASS Upgrade: a high-field tokamak for ITER- and DEMO-relevant research

COMPASS Upgrade: a high-field tokamak for ITER- and DEMO-relevant research

Digitizer hardware for magnetic data acquisition on COMPASS-U

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